Finite element modelling of the effect of temperature and neutron dose on the fracture behaviour of nuclear reactor graphite bricks

WADSWORTH, M., KYAW, Si and SUN, W. (2014). Finite element modelling of the effect of temperature and neutron dose on the fracture behaviour of nuclear reactor graphite bricks. Nuclear Engineering and Design, 280, 1-7.

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Official URL: http://www.sciencedirect.com/science/article/pii/S...
Link to published version:: https://doi.org/10.1016/j.nucengdes.2014.10.009
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    Abstract

    Graphite moderator bricks used within many UK gas-cooled nuclear reactors undergo harsh temperature and radiation gradients. They cause changes in material properties of graphite over extended periods of time. Consequently, models have been developed in order to understand and predict the complex stresses formed within the brick by these processes. In this paper the effect of irradiation temperature and neutron dose on the fracture characteristics, crack initiation and crack growth are investigated. A finite element (FE) mechanical constitutive model is implemented in combination with the damage model to simulate crack growth within the graphite brick. The damage model is based on a linear traction–separation cohesive model in conjunction with the extended finite element method for arbitrary crack initiation and propagation. Results obtained have showed that cracks initiate in the vicinity of the keyway fillet of the graphite brick and initiation time accelerates with higher temperatures and doses.

    Item Type: Article
    Departments - Does NOT include content added after October 2018: Faculty of Science, Technology and Arts > Department of Engineering and Mathematics
    Identification Number: https://doi.org/10.1016/j.nucengdes.2014.10.009
    Page Range: 1-7
    Depositing User: Si Kyaw
    Date Deposited: 23 Dec 2016 15:48
    Last Modified: 13 Jun 2017 13:55
    URI: http://shura.shu.ac.uk/id/eprint/14269

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